| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/09/2013 - 05/10/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48987 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: EXXON MOBILE CHEMICAL
Region: 4
City: BATON ROUGE State: LA
County:
License #: LA-2349-L01
Agreement: Y
Docket:
NRC Notified By: MELANIE BAUDER
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/01/2013
Notification Time: 09:43 [ET]
Event Date: 04/22/2013
Event Time: [CDT]
Last Update Date: 05/01/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK HAIRE (R4DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - SHUTTERS FOUND THAT WERE DIFFICULT TO OPERATE ON TWO PROCESS GAUGES
The following was received from the State of Louisiana via facsimile:
"On 4/22/2013, the Radiation Safety Officer (RSO) for ExxonMobile Chemical was performing his annual inventory and operational checks on the level gauges at the Baton Rouge facility. During the checks, two level gauges were found with shutters that were difficult to operate.
"The gauges detected were Ronan Engineering Gauges, devices involved, Model Number SAF-F37. One gauge is S/N 0781GK loaded with 100 mCi of Cs-137 and S/N 4585GH loaded with 25 mCi of Cs-137. Ronan Engineering has been contacted to fix the problem or repair the gauge. These gauges are installed on process and pose no safety threat to the general public or the employees. This is not considered a safety equipment failure, just being installed on a process in a very harsh corrosive environment.
"This is a two shutter malfunction on level gauges installed on processes. These devices do not pose a radiation exposure threat to the general public. They will remain in operation on the process until and after repair.
"The department considers this event closed."
Event Report ID No.: LA-120016, T146449 |
| Agreement State | Event Number: 48989 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: IRIS NDT MATRIX
Region: 4
City: GARYVILLE State: LA
County:
License #: LA-12236-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/01/2013
Notification Time: 13:28 [ET]
Event Date: 04/26/2013
Event Time: 14:57 [CDT]
Last Update Date: 05/01/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK HAIRE (R4DO)
FSME EVENT RESOURCES ()
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE FAILS TO RETRACT
The following information was received via fax:
"On 04/26/2013, the RSO for IRIS, was notified by one of his radiography crews working at the Marathon Refinery that a source was not retracting into the shielded area of the camera.
"This incident involved a QSA Global Exposure Device, Model Delta 880, S/N D6458, loaded with an Ir-192 source. Associated equipment was used with the exposure device. The problem occurred when the crew used a magnetic source tube stand as opposed to a non-magnetic support stand.
"Source retrieval was accomplished by the RSO around 2:53 pm. Using safety equipment, maintaining a 2 mR boundary, and time, the highest exposure received was by the RSO which was 75 mR. The other exposures recorded were from normal work activities. The Department [Louisiana Department of Environmental Quality] was notified after source retrieval was completed." |
| Fuel Cycle Facility | Event Number: 48990 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: DEREK WARFORD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/01/2013
Notification Time: 14:16 [ET]
Event Date: 04/30/2013
Event Time: 13:20 [CDT]
Last Update Date: 05/01/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(1) - UNPLANNED CONTAMINATION
| Person (Organization):
MICHELE SAMPSON (NMSS)
KATHLEEN O'DONOHUE (R2DO)
| Event Text AREA ACCESS RESTRICTED FOR MORE THAN 24 HOURS DUE TO INCREASED RADIOLOGICAL CONTROLS
"On 04/30/13, while changing the feed from Position 3 East to Position 3 West autoclaves, Operators noticed a pressure spike on the 3 East cylinder to approximately 47 psia. After disconnecting the cylinder in Position 3 East with Health Physics (HP) assistance, HP found a contamination spread on the cylinder, on the grating within the autoclave, and on the autoclave locking ring. Due to the contamination spread, access requirements to the area will be increased for more than 24 hours. Decontamination efforts are underway but will not be completed within 24 hours from the time that radiological controls were increased.
"This event is reportable as a 24 hour event in accordance with 10 CFR 76.120(c)(1)(i) 'An unplanned contamination event that: Requires access to the contaminated area, by workers or the public, to be restricted for more than 24 hours by imposing additional radiological controls or by prohibiting entry into the area.'
"The NRC Resident Inspector has been notified of this event." |
| Agreement State | Event Number: 48992 | Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: UNSPECIFIED
Region: 1
City: State: NY
County:
License #: UNSPECIFIED
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: PETE SNYDER | Notification Date: 05/02/2013
Notification Time: 13:31 [ET]
Event Date: 04/24/2013
Event Time: [EDT]
Last Update Date: 05/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GORDON HUNEGS (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - PROSTATE SEED IMPLANT EARLY TERMINATION
"A prostate seed implant procedure was terminated after the insertion of 2 needles. Only 5 of 106 intended seeds were implanted (1.55mCi of 32.86mCi). The patient's anatomy (pubic arch) presented interference to the placement of needles/seeds for proper dose distribution. The patient will now be treated with external beam IMRT [intensity modulated radiation therapy] once post implant CT and dose assessment have been performed in approximately 3 weeks. The patient and referring physician have been notified. The facility notified NYS DOH [New York State Department of Health] same day, written report with corrective actions has been received. To prevent recurrence the urologist will verify during planning volume study that there are no anatomical obstructions to needle placement."
Report No. NY-13-02
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Power Reactor | Event Number: 49012 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES MORGAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/09/2013
Notification Time: 00:09 [ET]
Event Date: 05/08/2013
Event Time: 21:47 [EDT]
Last Update Date: 05/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JAMES DWYER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP
The reactor automatically tripped at 2147 EDT. All control rods fully inserted on the trip and all systems responded as expected. Decay heat removal is to the main condenser. The plant is in its normal shutdown electrical lineup. The licensee is investigating the cause of the reactor trip.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49013 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN WHALLEY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/09/2013
Notification Time: 00:51 [ET]
Event Date: 05/08/2013
Event Time: 17:00 [EDT]
Last Update Date: 05/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMES DWYER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text MAIN ANNUNCIATOR SYSTEM INOPERABLE DUE TO MAINTENANCE
"On May 8, 2013 at 1700 hours with the reactor in a Cold Shutdown condition and the Reactor Mode Select Switch in Refuel, the main control room annunciator system became inoperable during a preplanned activity to repair the associated 120VAC/125 VDC instrument power supply transfer switching scheme. The reactor cavity is flooded, the fuel pool gates are removed, shutdown cooling is in service and reactor vessel reassembly activities are in progress. The appropriate abnormal procedure was entered and compensatory actions including periodic monitoring of bus voltages and field annunciator panels were implemented for systems in service at the time of the loss. Station risk is green and all key safety functions are green. Troubleshooting is in progress however, return to service time has not been determined.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii). The USNRC Resident Inspector has been notified. This event has no impact on the health and safety of the public." |
| Power Reactor | Event Number: 49014 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: GERRY RAUCH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/09/2013
Notification Time: 07:18 [ET]
Event Date: 05/09/2013
Event Time: 05:09 [CDT]
Last Update Date: 05/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE
"During Callaway refueling outage 19 on 5/8/13 at approximately 1900 hour CDT, water was observed dripping from piping insulation in the overhead by RCS loop 4. Further investigation determined it was near Safety Injection (EP) vent valve EPV0109. A scaffold was built and insulation was removed to perform an inspection. At approximately 0509 hours CDT on 5/9/13, engineering inspected the piping and determined there was a crack in the socket weld where 3/4 inch vent valve EPV0109 is connected to the 'B' train injection piping to RCS loop 4 Cold Leg. The estimated leakage rate through the crack is 6 (six) drops per minute. The configuration of this vent valve is a 3/8 inch flow restrictor socket welded to the six inch piping and a 3/4 inch vent valve socket welded to the flow restrictor. The crack is in the socket weld between the ASME code class 1 flow restrictor socket and the ASME code class 2 vent piping.
"Callaway plant was in mode 6 with refueling pool level greater than 23 feet above the reactor vessel flange at the time of the discovery. The 'A' RHR train which discharges to RCS loops 1 and 3 Cold Legs is the currently operable RHR train. 'B' RHR train was declared inoperable when the weld crack was identified. Only one RHR train is required to be operable at the present plant Mode of applicability. Repair plans are being developed.
"Basis for Reportability: This condition constitutes abnormal degradation of a principle safety barrier due to unacceptable welding defects within the primary coolant system."
There is a check valve between this leak and the reactor coolant system. Therefore, this is considered unisolable and pressure boundary leakage.
The licensee notified the NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 49015 | Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: ROSS LINDBERG
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/09/2013
Notification Time: 09:36 [ET]
Event Date: 05/08/2013
Event Time: 15:40 [CDT]
Last Update Date: 05/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
| Person (Organization):
DAVID AYRES (R2DO)
TIM MCCARTIN (NMSS)
| Event Text UNPLANNED MEDICAL TREATMENT OF CONTAMINATED INDIVIDUAL
"An employee reported to the dispensary yesterday afternoon with a potential knee injury at approximately 1540 CDT. The plant nurse administered first aid and decided to send the employee home. A whole body survey of the employee in his plant clothing was performed; the maximum amount of contamination was present on his right boot, 17,936 dpm/100 cm2. Prior to leaving the Restricted Area, the employee removed all plant clothing, changed into his personal clothing, and was re-surveyed. The employee was free of contamination upon release."
The licensee notified NRC R2 (Richard Gibson). |
| Power Reactor | Event Number: 49017 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL CZAYA
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 05/09/2013
Notification Time: 16:10 [ET]
Event Date: 03/11/2013
Event Time: 00:43 [EDT]
Last Update Date: 05/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
DAVID AYRES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 3 | Startup | 3 | Startup | Event Text INVALID ACTUATION OF THE AUXILIARY FEEDWATER SYSTEM
"This 60-day telephone notification is provided in accordance with 10 CFR 50.73(a)(1) to report an invalid actuation of the Unit 3 Auxiliary Feedwater (AFW) System reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A).
"On March 11,2013 at approximately 0043 [EDT], while starting the 3B Steam Generator Feed Pump (SGFP) for a one minute run, both trains of AFW started. Operators then manually closed the AFW flow control valves. AFW Trains 2 and 1 were restored to operable standby status at approximately 0112 [EDT] and 0117 [EDT], respectively.
"AFW actuation occurred because of a misunderstood procedure step and unnecessarily placed jumpers in AFW actuation logic in preparation for start of the 3B SGFP, which resulted in the invalid signal. At the time, the level in the steam generators was being maintained by the 3A Standby Steam Generator Feed Pump (SBSGFP).
"Because no actual loss of normal feedwater condition existed (with the 3A SBSGFP in service) which required AFW to start, and the start was not in response to actual plant conditions satisfying the requirements for actuation, this event is an invalid actuation."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 49019 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: CHRIS LAWS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/10/2013
Notification Time: 00:19 [ET]
Event Date: 05/09/2013
Event Time: 18:00 [PDT]
Last Update Date: 05/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INLET/OUTLET TURBIDITY FLOCCULATOR NOT RECORDING DATA
"The following is a non-emergency notification in accordance with 10CFR50.72(b)(2)(xi) due to the notification requirement to other government agencies that will be made within 48 hours.
"At 1800, May 9, 2013, the Columbia Generating Station main control room received notification that PWC-XR-1 had been found to be not recording data. A review of the stored data indicated that the data collection had been stopped since 5/2/2013 at 0934. The screen does show real time data, although that data is not being stored. Some of the data is recorded manually by chemistry technicians and operators during rounds that may be used for reporting purposes.
"Automatic functions for high turbidity shutdown and low chlorine setpoints remain active when the data is not being stored. The data collected by PWC-XR-1 includes inlet and outlet flocculator turbidity, water temperature, flow rate and free residual chlorine. Washington Administrative Code, WAC, 246-290-664 outlines the requirements for monitoring filtered systems. WAC 246-290-480 section 2.a requires this failure to be reported as a failure to comply with monitoring requirements to the Washington Department of Health within 48 hours.
"PWC-XR-1 data storage has been re-initiated and is working as expected."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49020 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/10/2013
Notification Time: 08:20 [ET]
Event Date: 05/10/2013
Event Time: 06:12 [EDT]
Last Update Date: 05/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
DAVID AYRES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 60 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO HIGH TURBINE BEARING VIBRATION
"On May 10, 2013 at 0612 hours [EDT], Unit 2 was manually tripped from 60% power due to increased vibrations and a report of arcing on bearing #9 of the main turbine. Unit 2 was in the process of increasing power following a refueling outage when this event occurred. The Operations crew entered the reactor trip procedure and stabilized Unit 2 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. This reactor protection system actuation is reportable per 10CFR50.72(b)(2)(iv)(B). The Auxiliary Feedwater pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater system is reportable per 10CFR50.72(b)(3)(iv)(A) for a valid actuation of an ESF system. The Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 2 is in a normal shutdown electrical lineup."
The #9 bearing is on the main generator exciter. There was no effect on Unit 1.
The licensee notified the NRC Resident Inspector and will be notifying local government agencies. | |